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Category:CORRESPONDENCE-LETTERS
MONTHYEARML18066A6871999-10-19019 October 1999 Forwards Response to NRC 990908 RAI Re Inservice Insp Program Relief Request 14.Ltr Contains No New Commitments & No Revs to Existing Commitments ML18066A6881999-10-19019 October 1999 Forwards Rev 5 to Palisades Nuclear Plant COLR, Per Requirements of TS 6.6.5.Ltr Contains No New Commitments & No Revs to Existing Commitments ML18066A6741999-10-0202 October 1999 Forwards MOR for Sept 1999 for Palisades Nuclear Plant & Operating Data Rept Sheet for Month of Aug 1999.MOR for Aug 1999 Inadvertently Had Copy of Ref Data Sheet for Apr 1999 Data ML18066A6791999-10-0101 October 1999 Provides Response to RAI Re Draft Rept, Study of Air- Operated Valves in Us Nuclear Power Plants. ML18066A6621999-09-30030 September 1999 Notifies NRC That Util Will Implement ITS at Plant on or Before Oct 31,2000 & Attachments 1 & 2 Contains Request for License Condition Which Relates First Performance of New or Revised Surveillance Requirements to Implementation of ITS ML18066A6601999-09-29029 September 1999 Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations. ML18066A6471999-09-17017 September 1999 Forwards Final Clean Copies of ITS & Bases Pages Which Incorporate All Changes Proposed in Listed Ltrs.Clean Copies Also Incorporate Some Editorial Changes & Bases Clarifications as Result of Ongoing Reviews to LCOs ML18066A6331999-09-0202 September 1999 Forwards Monthly Operating Rept for Aug 1999 & Revised Monthly Operating Rept for Apr 1999 for Palisades Nuclear Plant ML18066A6261999-08-26026 August 1999 Forwards Addl New Valve Relief Request as Alternative to Code Requirements That Will Provide Acceptable Level of Quality & Safety.Request Would Allow Use of App II, Check Valve Condition Monitoring Program, of ASME OM Code-1995 ML20211D5661999-08-17017 August 1999 Forwards semi-annual Fitness for Duty Program Performance Rept for 990101-990630,IAW 10CFR26.71(d).Attachments 1 & 2 Summarize Test Results at Palisades Plant,Big Rock Point Plant & Corporate Ofc ML18066A6111999-08-13013 August 1999 Requests Exemption from Certain Requirements of 10CFR50,App R, Fire Protection Program for Nuclear Power Facilities Operating Prior to 790101. Request Concerns Oil Collection Sys Requirements for PCP Motors ML18066A5881999-07-30030 July 1999 Provides Rev to Instrument Channel Drift Measurement Submitted on 990611,in Response to NRC Comments on Util RAI Response for Sections 3.3,3.5 & 3.6 & Editorial Changes Revs Necessary for Consistency within ITS ML18066A5921999-07-30030 July 1999 Forwards Results of Review by Consumers Energy of Two NRC Draft Repts Entitled, Evaluation of Air-Operated Valves at Light-Water Reactors & Study of Air-Operated Valves in Us Nuclear Power Plants. ML18066A5971999-07-30030 July 1999 Forwards Markup of Draft NRC SE Re Util Proposal to Convert to Its.Ltr Contains No New Commitments & No Revs to Existing Commitments ML20210G8351999-07-29029 July 1999 Final Response to FOIA Request for Documents.Records in App a Encl & Will Be Available in PDR ML18066A5651999-07-19019 July 1999 Forwards Corrections to Previously Submitted TS Section 3.7, Plant Systems, Converting to Its,Per NUREG-1432.Licensee Realized That Certain Provisions of CTS Had Been Inappropriately Replaced with Provisions from STS ML18066A5111999-06-29029 June 1999 Provides Voluntary Confirmation of Facility Readiness as Outlined in GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. Disclosure & Response Encl ML20209B2081999-06-29029 June 1999 Discusses Closure of Response to RAI Re GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity. Rvid,Version 2 Issued as Result of Review of Responses.Info Should Be Reviewed & Comments Submitted by 990901 ML20210G8791999-06-23023 June 1999 FOIA Request for All Document Communications Between NRC & Region III Involving R Landsman,B Jorgensen & R Caniano & NRC Staff Under Their Supervision & All Communications in Their Possession to & from Consumers Power Re Plant ML18066A5061999-06-17017 June 1999 Forwards Responses to NRC Questions for ITS LCOs 3.6.3 & 3.6.6 of 990126 Submittal.One Editorial Change in Addition to Those Made in Response to NRC Comments & Conforming Changes Made to Associated Bases,Encl ML18066A4991999-06-11011 June 1999 Forwards Responses to NRC Comments Re ITS Section 3.3 & Associated Revs to ITS Sections 1.0,3.3,3.4 & 3.9 of 990126 ITS Conversion Submittal.One Technical Change & Several Editorial Changes Unrelated to NRC Comments,Also Provided IR 05000255/19970181999-06-0909 June 1999 Discusses Response of 980226 Violation Re Insp Rept 50-255/97-18 Re Failure to Take Adequate Corrective Action. Ltr Contains New Commitments & No Rev ML18066A4921999-06-0909 June 1999 Discusses Response of 980226 Violation Re Insp Rept 50-255/97-18 Re Failure to Take Adequate Corrective Action. Ltr Contains New Commitments & No Rev ML18068A6011999-06-0808 June 1999 Forwards Description of Recent Changes Made to Palisades Site Emergency Plan,Excluding Minor & Editorial Changes Not Requiring Further Explanation ML18066A4881999-06-0404 June 1999 Provides Responses to NRC Questions & Associated Editorial Revs for ITS LCOs 3.6.1,3.6.2,3.6.4,3.6.5 & 3.6.7 of 980126 Submittal.Responses to Comments on Remaining Section 3.6 LCOs Will Be Submitted Separately ML18066A4801999-05-24024 May 1999 Forwards Copy of Rev to NPDES Permit Number MI0001457 Renewal Application as Submitted to Mi Dept of Environ Quality on 990513 ML18066A4721999-05-18018 May 1999 Informs That During Period from 981101-990430,there Were No NPDES Permit Violations & No Repts of Oil,Salt or Polluting Matl Losses Were Made to Govt Agencies ML18066A4651999-05-17017 May 1999 Forwards ISI Program Relief Request 14 for NRC Approval in Accordance with 10CFR50.55(a)(3) as Requirement for Which Proposed Alternative Provide Acceptable Level of Quality & Safety.Rev 0 to SIR-99-032 Rept Also Encl ML18066A4611999-05-14014 May 1999 Requests Approval to Use Alternative Requirements IAW 10CFR50.55a(a)(3)(i),proposing to Follow Requirements of ASME Boiler & Pressure Vessel Code Case N-566-1.IST Program Relief Request 6 for NRC Approval Encl ML18068A5831999-05-0303 May 1999 Forwards Proposed TS Section 3.5,in Response to NRC 990317 RAI Re Util 980126 TS Change Request Re Conversion to Improved Ts,Per NUREG-1432 ML20206J2411999-04-30030 April 1999 Submits Corrected Copy of Ltr Forwarding 1998 Consumers Energy Co Annual Rept. Ltr Contains Corrected Docket & License Number for Big Rock Point.With One Oversize Encl ML20217A8191999-04-29029 April 1999 Forwards Listed Matls Related to Palisades Plant June 1999 Initial License Exam ML20206E8271999-04-28028 April 1999 Forwards Palisades Plant Annual Radiological Environ Operating Rept for 1998. There Were No Reportable Events During This Period ML20207B4661999-04-23023 April 1999 Forwards Copy of Final Exercise Rept for Biennial Radiological Emergency Preparedness Exercise Conducted on 981201 for Palisades Npp.No Deficiencies Noted.Seven New Arcas Identified ML18066A4531999-04-0707 April 1999 Forwards ITS Pages 3.1.4-2 & 3.1.4-8,revising Completion Time for Action D.1,as Requested by NRC 990406 Telcon,Per TS Change Request Submitted 980126.Change Submitted Does Not Alter Conclusions of No Signficant Hazards Considerations ML18066A4481999-04-0202 April 1999 Responds to Violations Noted in Insp Rept 50-255/98-06. Corrective Actions:Nuclear Performance Assessment Dept Has Reviewed Observations & Agrees That Field Observations by Qualified Personnel Are Important Aspect of Program ML18066A4471999-03-30030 March 1999 Confirms Completion of Util Review of Design Engineering Contractor Cable Ampacity Evaluation.Evaluation Available at Plant for NRC Review ML18066A4411999-03-30030 March 1999 Forwards Response to NRC 990126 RAI Re TS Section 3.7 of Util 980126 LAR Request for Conversion to Its.Licensee Received Permission to Delay TS Section 3.6 Response to Allow for Addl Time for Preparation & Internal Review ML18066A4441999-03-26026 March 1999 Submits Certification of Financial Assurance for Decommissioning of Palisades Nuclear Plant.Certified Rept of Status of Consumers Energy Co Decommissioning Funding & Trust Agreement Encl as Attachments 1 & 2 ML18066A4401999-03-25025 March 1999 Forwards Revised Best Estimate Fluence Evaluation Using Industry Data, Providing Justification for Using Industry Data to Determine Best Estimate Fluence.Review of Info & SE Requested ML18066A4191999-03-23023 March 1999 Forwards 1998 Annual Radioactive Effluent Release & Disposal Rept, for Palisades Plant,Providing Summary of Quantities of Radioactive Liquid & Gaseous Effluent Releases & Solid Radioactive Waste Processed During 1998 ML18066A4231999-03-22022 March 1999 Forwards Answers to 990311 Telcon Request for Addl Clarification & Revs Re ITS Section 3.4.Markups of Previously Submitted TS Pages & Revised Pages for Section 3.4 Also Encl ML20204F2091999-03-18018 March 1999 Requests That Listed TS Change Requests (Tscrs) Be Issued with Allowance That Tscrs Be Fully Implemented within Sixty Days of Issuance.Request Will Allow Time for Completion of Final Training & Procedure Changes Associated with Amend ML18066A4121999-03-18018 March 1999 Concludes That Mod to Provide Automatic Switchover of Control Room Heating,Ventilation & Air Conditioning (CRHVAC) Sys to Emergency Mode Is Not Needed to Meet Regulatory Requirements.Mod Commitment Cancelled ML18066A4141999-03-18018 March 1999 Forwards Rev 4 to COLR, Containing Limits for Fuel Cycle 14 & Future Cycles ML20204E5861999-03-16016 March 1999 Submits Current Limits of Property Insurance Maintained at Consumers Energy Co Operating Nuclear Power Plants ML18066A4131999-03-11011 March 1999 Responds to NRC 990210 Ltr Re Violations Noted in Insp Rept 50-255/98-22.Corrective Actions:Analytical Evaluation, EA-C-PAL-98-1067-01, P-50A Case to Cover Stud Evaluation, Was Submitted to NRC on 981220 ML18068A5241999-02-12012 February 1999 Resubmits Relief Request 12,with Addl Info That Includes Specific Locations Where Relief Request Would Be Applied,Per 10CFR50.55a(g)(5)(iii) ML18068A5211999-02-11011 February 1999 Informs NRC That Implementation of Formal Industry Position on Severe Accident Mgt at Palisades Plant Was Completed on 981217 ML20203F2541999-02-10010 February 1999 Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function 1999-09-30
[Table view] Category:ENGINEERING/CONSTRUCTION/CONSULTING FIRM TO NRC
MONTHYEARML20237B8051987-11-25025 November 1987 FOIA Request That Encls to Listed Documents,Including NRC Forwarding Amend 1 to License NPF-73,be Placed in PDR ML20238E3011987-06-29029 June 1987 FOIA Request for All Documents Described in App,Including Listed LERs & Revs for Plants,W/Original Attachments & Encls ML18052B1911987-06-17017 June 1987 Forwards EGG-NTA-7720, Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28,Reactor Trip Sys Vendor Interface:Calvert Cliffs-1 & -2,Millstone-2 & Palisades, Final Informal Rept. Plants Conform to Generic Ltr Item ML18052B1531987-05-0101 May 1987 Forwards Final EGG-NTA-7622, Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components:Palisades, Informal Rept ML18052B0521987-04-17017 April 1987 Forwards EGG-NTA-7439, Conformance to Generic Ltr 83-28, Item 2.2.1 -- Equipment Classification for All Other Safety- Related Components:Palisades, Final Rept.Facility Conforms to Generic Ltr on Item ML18052B0491987-03-30030 March 1987 Forwards EGG-NTA-7484, Technical Evaluation Rept for Palisades Plant,Response to NRR Generic Ltr 83-37, Interim Rept.Licensee Not in Compliance W/Control Room Habitability Requirement (III.D.3.4).Items Still Under Review Listed ML20209F8601987-01-15015 January 1987 Requests Publicly Available Copies of Handouts or Viewgraphs Used at Region III Meeting 05000255/LER-1950-255, FOIA Request for 851118 LER 50-255/85-23 on Possible Low Temp Overpressure Sys Setpoint Error to Be Placed in PDR1986-02-26026 February 1986 FOIA Request for 851118 LER 50-255/85-23 on Possible Low Temp Overpressure Sys Setpoint Error to Be Placed in PDR ML20078A1601983-06-0101 June 1983 FOIA Request for 821021 Document Re Palisades 820204 Cooling Tower Pump Trip & 821117 Document Re San Onofre 2 Auxiliary Feedwater Pump Vent Failure ML18047A6851982-12-0909 December 1982 Forwards, Sep,High Energy Line Breaks Inside Containment, Palisades Nuclear Station,Phase IV Summary of Results, Revision 0. Rept Incorporates Results of Fracture Mechanics Analysis ML17309A2771982-06-28028 June 1982 Repts Under Purchase Order DR-82-0961 Re Review of Two Draft SEP Integrated Assessments for Facilities.Ltr Comprises Rept on Ginna SEP (Draft NUREG-0821) ML18047A3291982-04-23023 April 1982 Submits Draft Review of Integrated Plant Safety Assessment of Sep.Review of Operating Experiences Needs to Be Updated & Augmented ML18047A2841982-04-15015 April 1982 Submits Review of Draft NUREG-0820, Integrated Plant Safety Assessment:Sep,Palisades Plant. Addl Matl May Be Provided at Later Date ML19343C1641980-11-0909 November 1980 Responds to ACRS 800918 Request for Comment on B Cohen Concerns Re Refueling Water Storage Tank Adequacy.Decay Heat Removal Alternatives Recommended ML18045A4521980-07-28028 July 1980 Forwards Draft of SEP Review of NRC Safety Topic VI-7.B Associated W/Electrical,Instrumentation & Control Portion of Engineered Safety Feature Switchover from Injection to Recirculation Mode for Palisades Nuclear Power Plant. ML18045A4511980-07-28028 July 1980 Forwards Rough Draft Rept Detailing NRC Safety Topic VII-2, Engineered Safety Feature Sys Control Logic & Design. Requests Comments & Recommendations ML18045A4501980-07-28028 July 1980 Forwards Draft Rept on Plant Detailing NRC Safety Topic III-1 Re Classifications of Structrues,Components & Sys ML20084U7531972-11-0808 November 1972 Comments on Requesting Addl Info on Main Steam Safety Valves.Angle of Discharge,Stress Analysis,Dynamic Load Factor & Header Stress Discussed ML20084U5051972-11-0808 November 1972 Comments on 721031 Response to Questions Re Main Steam Safety Valves.Response by Util Not Acceptable 1987-06-29
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML18066A6871999-10-19019 October 1999 Forwards Response to NRC 990908 RAI Re Inservice Insp Program Relief Request 14.Ltr Contains No New Commitments & No Revs to Existing Commitments ML18066A6881999-10-19019 October 1999 Forwards Rev 5 to Palisades Nuclear Plant COLR, Per Requirements of TS 6.6.5.Ltr Contains No New Commitments & No Revs to Existing Commitments ML18066A6741999-10-0202 October 1999 Forwards MOR for Sept 1999 for Palisades Nuclear Plant & Operating Data Rept Sheet for Month of Aug 1999.MOR for Aug 1999 Inadvertently Had Copy of Ref Data Sheet for Apr 1999 Data ML18066A6791999-10-0101 October 1999 Provides Response to RAI Re Draft Rept, Study of Air- Operated Valves in Us Nuclear Power Plants. ML18066A6621999-09-30030 September 1999 Notifies NRC That Util Will Implement ITS at Plant on or Before Oct 31,2000 & Attachments 1 & 2 Contains Request for License Condition Which Relates First Performance of New or Revised Surveillance Requirements to Implementation of ITS ML18066A6601999-09-29029 September 1999 Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations. ML18066A6471999-09-17017 September 1999 Forwards Final Clean Copies of ITS & Bases Pages Which Incorporate All Changes Proposed in Listed Ltrs.Clean Copies Also Incorporate Some Editorial Changes & Bases Clarifications as Result of Ongoing Reviews to LCOs ML18066A6331999-09-0202 September 1999 Forwards Monthly Operating Rept for Aug 1999 & Revised Monthly Operating Rept for Apr 1999 for Palisades Nuclear Plant ML18066A6261999-08-26026 August 1999 Forwards Addl New Valve Relief Request as Alternative to Code Requirements That Will Provide Acceptable Level of Quality & Safety.Request Would Allow Use of App II, Check Valve Condition Monitoring Program, of ASME OM Code-1995 ML20211D5661999-08-17017 August 1999 Forwards semi-annual Fitness for Duty Program Performance Rept for 990101-990630,IAW 10CFR26.71(d).Attachments 1 & 2 Summarize Test Results at Palisades Plant,Big Rock Point Plant & Corporate Ofc ML18066A6111999-08-13013 August 1999 Requests Exemption from Certain Requirements of 10CFR50,App R, Fire Protection Program for Nuclear Power Facilities Operating Prior to 790101. Request Concerns Oil Collection Sys Requirements for PCP Motors ML18066A5971999-07-30030 July 1999 Forwards Markup of Draft NRC SE Re Util Proposal to Convert to Its.Ltr Contains No New Commitments & No Revs to Existing Commitments ML18066A5881999-07-30030 July 1999 Provides Rev to Instrument Channel Drift Measurement Submitted on 990611,in Response to NRC Comments on Util RAI Response for Sections 3.3,3.5 & 3.6 & Editorial Changes Revs Necessary for Consistency within ITS ML18066A5921999-07-30030 July 1999 Forwards Results of Review by Consumers Energy of Two NRC Draft Repts Entitled, Evaluation of Air-Operated Valves at Light-Water Reactors & Study of Air-Operated Valves in Us Nuclear Power Plants. ML18066A5651999-07-19019 July 1999 Forwards Corrections to Previously Submitted TS Section 3.7, Plant Systems, Converting to Its,Per NUREG-1432.Licensee Realized That Certain Provisions of CTS Had Been Inappropriately Replaced with Provisions from STS ML18066A5111999-06-29029 June 1999 Provides Voluntary Confirmation of Facility Readiness as Outlined in GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. Disclosure & Response Encl ML20210G8791999-06-23023 June 1999 FOIA Request for All Document Communications Between NRC & Region III Involving R Landsman,B Jorgensen & R Caniano & NRC Staff Under Their Supervision & All Communications in Their Possession to & from Consumers Power Re Plant ML18066A5061999-06-17017 June 1999 Forwards Responses to NRC Questions for ITS LCOs 3.6.3 & 3.6.6 of 990126 Submittal.One Editorial Change in Addition to Those Made in Response to NRC Comments & Conforming Changes Made to Associated Bases,Encl ML18066A4991999-06-11011 June 1999 Forwards Responses to NRC Comments Re ITS Section 3.3 & Associated Revs to ITS Sections 1.0,3.3,3.4 & 3.9 of 990126 ITS Conversion Submittal.One Technical Change & Several Editorial Changes Unrelated to NRC Comments,Also Provided IR 05000255/19970181999-06-0909 June 1999 Discusses Response of 980226 Violation Re Insp Rept 50-255/97-18 Re Failure to Take Adequate Corrective Action. Ltr Contains New Commitments & No Rev ML18066A4921999-06-0909 June 1999 Discusses Response of 980226 Violation Re Insp Rept 50-255/97-18 Re Failure to Take Adequate Corrective Action. Ltr Contains New Commitments & No Rev ML18068A6011999-06-0808 June 1999 Forwards Description of Recent Changes Made to Palisades Site Emergency Plan,Excluding Minor & Editorial Changes Not Requiring Further Explanation ML18066A4881999-06-0404 June 1999 Provides Responses to NRC Questions & Associated Editorial Revs for ITS LCOs 3.6.1,3.6.2,3.6.4,3.6.5 & 3.6.7 of 980126 Submittal.Responses to Comments on Remaining Section 3.6 LCOs Will Be Submitted Separately ML18066A4801999-05-24024 May 1999 Forwards Copy of Rev to NPDES Permit Number MI0001457 Renewal Application as Submitted to Mi Dept of Environ Quality on 990513 ML18066A4721999-05-18018 May 1999 Informs That During Period from 981101-990430,there Were No NPDES Permit Violations & No Repts of Oil,Salt or Polluting Matl Losses Were Made to Govt Agencies ML18066A4651999-05-17017 May 1999 Forwards ISI Program Relief Request 14 for NRC Approval in Accordance with 10CFR50.55(a)(3) as Requirement for Which Proposed Alternative Provide Acceptable Level of Quality & Safety.Rev 0 to SIR-99-032 Rept Also Encl ML18066A4611999-05-14014 May 1999 Requests Approval to Use Alternative Requirements IAW 10CFR50.55a(a)(3)(i),proposing to Follow Requirements of ASME Boiler & Pressure Vessel Code Case N-566-1.IST Program Relief Request 6 for NRC Approval Encl ML18068A5831999-05-0303 May 1999 Forwards Proposed TS Section 3.5,in Response to NRC 990317 RAI Re Util 980126 TS Change Request Re Conversion to Improved Ts,Per NUREG-1432 ML20206J2411999-04-30030 April 1999 Submits Corrected Copy of Ltr Forwarding 1998 Consumers Energy Co Annual Rept. Ltr Contains Corrected Docket & License Number for Big Rock Point.With One Oversize Encl ML20217A8191999-04-29029 April 1999 Forwards Listed Matls Related to Palisades Plant June 1999 Initial License Exam ML20206E8271999-04-28028 April 1999 Forwards Palisades Plant Annual Radiological Environ Operating Rept for 1998. There Were No Reportable Events During This Period ML20207B4661999-04-23023 April 1999 Forwards Copy of Final Exercise Rept for Biennial Radiological Emergency Preparedness Exercise Conducted on 981201 for Palisades Npp.No Deficiencies Noted.Seven New Arcas Identified ML18066A4531999-04-0707 April 1999 Forwards ITS Pages 3.1.4-2 & 3.1.4-8,revising Completion Time for Action D.1,as Requested by NRC 990406 Telcon,Per TS Change Request Submitted 980126.Change Submitted Does Not Alter Conclusions of No Signficant Hazards Considerations ML18066A4481999-04-0202 April 1999 Responds to Violations Noted in Insp Rept 50-255/98-06. Corrective Actions:Nuclear Performance Assessment Dept Has Reviewed Observations & Agrees That Field Observations by Qualified Personnel Are Important Aspect of Program ML18066A4471999-03-30030 March 1999 Confirms Completion of Util Review of Design Engineering Contractor Cable Ampacity Evaluation.Evaluation Available at Plant for NRC Review ML18066A4411999-03-30030 March 1999 Forwards Response to NRC 990126 RAI Re TS Section 3.7 of Util 980126 LAR Request for Conversion to Its.Licensee Received Permission to Delay TS Section 3.6 Response to Allow for Addl Time for Preparation & Internal Review ML18066A4441999-03-26026 March 1999 Submits Certification of Financial Assurance for Decommissioning of Palisades Nuclear Plant.Certified Rept of Status of Consumers Energy Co Decommissioning Funding & Trust Agreement Encl as Attachments 1 & 2 ML18066A4401999-03-25025 March 1999 Forwards Revised Best Estimate Fluence Evaluation Using Industry Data, Providing Justification for Using Industry Data to Determine Best Estimate Fluence.Review of Info & SE Requested ML18066A4191999-03-23023 March 1999 Forwards 1998 Annual Radioactive Effluent Release & Disposal Rept, for Palisades Plant,Providing Summary of Quantities of Radioactive Liquid & Gaseous Effluent Releases & Solid Radioactive Waste Processed During 1998 ML18066A4231999-03-22022 March 1999 Forwards Answers to 990311 Telcon Request for Addl Clarification & Revs Re ITS Section 3.4.Markups of Previously Submitted TS Pages & Revised Pages for Section 3.4 Also Encl ML20204F2091999-03-18018 March 1999 Requests That Listed TS Change Requests (Tscrs) Be Issued with Allowance That Tscrs Be Fully Implemented within Sixty Days of Issuance.Request Will Allow Time for Completion of Final Training & Procedure Changes Associated with Amend ML18066A4141999-03-18018 March 1999 Forwards Rev 4 to COLR, Containing Limits for Fuel Cycle 14 & Future Cycles ML18066A4121999-03-18018 March 1999 Concludes That Mod to Provide Automatic Switchover of Control Room Heating,Ventilation & Air Conditioning (CRHVAC) Sys to Emergency Mode Is Not Needed to Meet Regulatory Requirements.Mod Commitment Cancelled ML20204E5861999-03-16016 March 1999 Submits Current Limits of Property Insurance Maintained at Consumers Energy Co Operating Nuclear Power Plants ML18066A4131999-03-11011 March 1999 Responds to NRC 990210 Ltr Re Violations Noted in Insp Rept 50-255/98-22.Corrective Actions:Analytical Evaluation, EA-C-PAL-98-1067-01, P-50A Case to Cover Stud Evaluation, Was Submitted to NRC on 981220 ML18068A5241999-02-12012 February 1999 Resubmits Relief Request 12,with Addl Info That Includes Specific Locations Where Relief Request Would Be Applied,Per 10CFR50.55a(g)(5)(iii) ML18068A5211999-02-11011 February 1999 Informs NRC That Implementation of Formal Industry Position on Severe Accident Mgt at Palisades Plant Was Completed on 981217 ML18066A4051999-02-10010 February 1999 Requests Copy of Consumers Energy (Palisades) Formal Response to RAI Dtd 990512 (USI A-46) ML18066A3921999-01-29029 January 1999 Forwards Licensee Interpretation of TS Requirements for Performance of SRs as Applied to Instrumentation Channel Calibr.Ltr Established No New Commitments ML18066A3891999-01-28028 January 1999 Submits Response to Concern Expressed in Insp Rept 50-255/98-06 Re Whether Palisades ISI Program Was Being Conducted IAW Applicable Requirements 1999-09-30
[Table view] |
Text
, Page 1 of 4 n
\.)
and Attachment -1 a ra m e ter, snh c.
r Consulting Encinocrs
- Design - Analysis - Development 13543 WATERTOWN PLANC ROAD, ELM GROYf, W4SCONSIN 33122 786-7583 November 8, 1972 Mr. G. W. Reinmuth, Chief Technical Assistance Branch United States Atomic Energy Commission Directorate of Regulatory Operations l Washington, D. C. 20545 Copy: L. L. Beratan l
Reference:
AEC Contract AT(11-1)-1658 Task A, Consulting Services
, PAR: 72-73 A Assignment No. DC-102
Subject:
Review of Consumers Power Company letter of October 31, 1972 replying to questions on Palisades main steam safety valves
Dear Mr. Reinmuth:
1 The following comments apply to the eight points in the subject letter which in turn correspond to the questions set forth in the Regulatory document entitled " Request for Additional Information - Consumers Power Co.,
Palisades Plant Docket No. 50-255 :
1 The information provided is not responsive to the question which asked for justification of the thrust angle assumed. We do not feel that the discharge elbow has a long enough radius to turn the steam 570 or even 450 Looking through the elbow into the throat of the valve, a line of sight with an area approximately 4CT of the elbow cross section exists at an angle of about 270 above the horizontal (equal to a deflection of 300 from the 570 line).
h$$
wo The 120 deviation allowed by the analysis does not So relate to a maximum angle of deficction that has been by demonstrated to result from valve discharge. Because Q(g the stress levels in both the elbow and header (See Attachment -1) are sensitive to the angic assumed in mo the analysis, it is of utmost importance to justify Y the maximum angle of deflection expected as a starting 8$ point. It appears that this has not been done, c)o.a.
The fact that an angle of only 120 is allowed within
- A rim a ,, 3,.c. O o ?>ce -2 C O N S U LTI N G E N GI N E E R S ELM G R O V E, WISCONSIN Mr. G. W. Reinmuth -
USAEC-RO November 8, 1972 B31.1 stress limits indicates that the design is less conservative than originally thought by the licensee.
(This allowable angle was reported as 22.80 in the CP letter of September 15, and report verbally as 17.50 by the Bechtel representative in the September 27 meeting at Bethesda.) ,
- 2. Without reviewing the analysis, it is not possible to comment on the calculated maximum discharge force of 14,200 lbs. It seems reasonable in terms of data published by Crosby. The investigation should have looked into the effect of steam discharging at an angle flatter than the 57 and impinging on the separately supported dishcarge stack.
- 3. The basis for calculation of a dynamic load factor appears adequate. It is agreed that the com-binadstresses using the load factor can be compared with the material yield strength,which is comparable to 1.5Sa, This is a technical evaluation which goes beyond the applicable Code, B31.1.
- 4. As developed in our report, DC-102, September 25, 1972, the 1/2" reinforcing pad does not contribute significantly to header stiffness or reduction of Bijlaard stresses. We do not feel that it is correct to use the total thickness of 1.75" which includes pad in the stress calculation, except possibly for the pressure stress component. The results of analyses which we consider more accurate, but possibly somewhat conservative are presented in Attachment -1. We believe the licensee's calculation defines a lower bound for stress levels at the weld-o-let to header connection, rather than an " upper bound".
- 5. No Comment.
Page -3
' pa r a,m e!a r, c n c. o O C O N S U LTI N G E N GIN E E 2 5 ELM GROVE, Wl5 CON 5tN Mr. G. W. Reinmuth USAEC-RO November 8, 1972
- 6. A review of Attachment -A, indicates that the 1.3 dynamic load factor was apparently not applied in calculation of the longitudinal stresses reported for locations a_, b, and c. Our calculations show some-what higher stresses without the factor, the discrep-ancy being attributed to determination of the length of the moment arms in scaling the Be c htel layout drawing No. M-79, Rev. O.
We calculated stresses at location d, using the
" assumed 1.75" header wall" and have duplicated the stated results. In this case, it appears that the 1.3 dynamic load factor was applied. Stresses at location e, were not checked. Our previcus work in report DC-102, indicated that the stresses at the location e, were generally lower than at d,. The duplication of the licensee's reported 26,280 psig header stress at point d, does not indicate our concurrence. As indicated in Item -4 above, the value results from an assumption of an equivalent 1.75" wall thickness which is considered to be grossly non-conservative.
The answer to question (6) indicates that the Summary of Stresses assumes the " smallest justifiable" thrust angle. As indicated in (1) above, this angle is not considered to have been " justified".
- 7. Contained in this response is a statement that
"----the design conforms to Code within the degree of conservatism inherent in the assumptions made." It is two of these assumptions which give us a problem.
First is the assumption that "---the blowoff thrust would acc perpendicular to the face of the discharge surface." (or vary no mare than 120). The second is that the 1.75" combined thickness of the header wall
, and pad can be used in the Bijlaard calculation of stresses directly.
"""^
l l A,.:-cu,, L. O O C O N S U LTI N G E N GI Ni E R 5 ELM GROVE, WIS C O N 5 t N Mr. G. W. Reinmuth _
USAEC-RO November 8, 1972 The third paragraph under (7) presents the pot.sibility of applying the 3S m limit to safety valve discharge stresses treated as primary plus secondary stresses.
While the Code is not explicit on this, we do not believe that these stresses can be considered self-limiting and were satisfied to see that this rationale was not followed. We are in agreement with the limit of.1.SSm stated as being more appropriate in the fourth
, paragraph.
The'fifth paragraph under (7) indicates that a conser-vative margin is available in B31.1 stress levels to compensate for any deviation in the thrust angle. While no order of magnitudes are given, we do not believe that l credit can be taken for any conservatism in the Code.
For example, the non-conservative reported stress of 26,280 psi for the header at location d_ is beyond the 3 imits of 1.2Sh strictly allowd by R'11.1 and must be l compared with 1.SSm using methods which go beyond B31.1.
We do not understand the applicability of the last paragraph under (7) which talks of cyclic life. It would seem to imply that the system is good for 100,000 cycles. A specific fatigue evaluation applied to the highest stressed area would show a life orders of magnitude lower.
- 8. Stresses in the header, other than local at the safety valve connection, were not included in the scope of PARAMETER 's review on this assignment . We have no comments as to the contribution of valve reaction forces to general piping stresses.
If you have any questions or require any additional detail.
in this matter, please let me know.
Very truly yours, 4 , i TER, nc.
b M <
Richard A. Lofy Consulting Engineer Q
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